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| {{#Wiki_filter:Enclosure 7 to SBK-L-15073Non-Proprietary Class 3 Westinghouse Report (PWROG-15023-NP, Revision 1)Seabrook Station Unit 1 Summary ReportFor the Fuel Design/Fuel Management Assessments toDemonstrate MRP-227-A Applicability(Non-Proprietary) | | {{#Wiki_filter:Enclosure 7 to SBK-L-15073 Non-Proprietary Class 3 Westinghouse Report (PWROG-15023-NP, Revision 1)Seabrook Station Unit 1 Summary ReportFor the Fuel Design/Fuel Management Assessments toDemonstrate MRP-227-A Applicability (Non-Proprietary) |
| .Rý.R :E1 SS- U R I Z E DPWROG'WAT E R R EýACjTO R R S G R.O U PPWROG.1I5023-NPIA Revi sionI" '... ... ...: : : ---. ............ .....-... ." : .: ., ' : ; ..--..: ..v ! : .WESTINGHOUSE NON-PROPRIETARY CLASS 3Seabrook Station Unit 1 SummaryReport for the Fuel Design / FuelManagement Assessments toDemonstrate MRP-227-AApplicabilityMaterials CommitteePA-MSC-0983, Revision. 1,Task 7May 2015Westinghouse WESTINGHOUSE NON-PROPRIETARY CLASS 3PWROG-15023-NPRevision 1Seabrook Station Unit I SummaryReport for the Fuel Design I FuelManagement Assessments toDemonstrate MRP-227-A ApplicabilityPA-MSC-0983, Revision 1, Task 70983, Revision 1,Task 7Justin T. Figley*Safety Analysis and Licensing / LOCA Integrated Services IIMay 2015Reviewer: Jianwei Chen*Radiation Engineering and AnalysisApproved: Laurent P. Houssay*, ManagerRadiation Engineering and AnalysisApproved: James P. Molkenthin*, Program DirectorPWR Owners Group PMO*Electronically approved records are authenticated in the electronic document management system.Westinghouse Electric Company LLC1000 Westinghouse DriveCranberry Township, PA 16066, USA© 2015 Westinghouse Electric Company LLCAll Rights Reserved WESTINGHOUSE NON-PROPRIETARY CLASS 3iiiACKNOWLEDGEMENTSThis report was developed and funded by the Pressurized Water Reactor Owners Group underthe leadership of the participating utility representatives of the Materials Committee.PWROG-15023-NPMay 2015Revision 1 WESTINGHOUSE NON-PROPRIETARY CLASS 3ivLEGAL NOTICEThis report was prepared as an account of work performed by Westinghouse ElectricCompany LLC. Neither Westinghouse Electric Company LLC, nor any person acting on itsbehalf:1. Makes any warranty or representation, express or implied including the warranties offitness for a particular purpose or merchantability, with respect to the accuracy,completeness, or usefulness of the information contained in this report, or that the use ofany information, apparatus, method, or process disclosed in this report may not infringeprivately owned rights; or2. Assumes any liabilities with respect to the use of, or for damages resulting from the useof, any information, apparatus, method, or process disclosed in this report.COPYRIGHT NOTICEThis report has been prepared by Westinghouse Electric Company LLC and bears aWestinghouse Electric Company copyright notice. As a member of the PWR Owners Group, youare permitted to copy and redistribute all or portions of the report within your organization;however all copies made by you must include the copyright notice in all instances.DISTRIBUTION NOTICEThis report was prepared for the PWR Owners Group. This Distribution Notice is intended toestablish guidance for access to this information. This report (including proprietary andnon-proprietary versions) is not to be provided to any individual or organization outside of thePWR Owners Group program participants without prior written approval of the PWR OwnersGroup Program Management Office. However, prior written approval is not required for programparticipants to provide copies of Class 3 Non-Proprietary reports to third parties that aresupporting implementation at their plant, and for submittals to the NRC.PWROG-1 5023-NP May 2015PWROG-1 5023-NPMay 2015Revision 1 WESTINGHOUSE NON-PROPRIETARY CLASS 3VTABLE OF CONTENTSMRP 2013-025 GUIDANCE TEXT DEMONSTRATING MRP-227-A APPLICABILITYFOR SEABROOK UNIT 1 REACTOR INTERNALS AGING MANAGEMENT FUELDESIGN / FUEL MANAGEMENT ASSESSMENTS ...................................................... 1-11.1 SEABROOK UNIT 1 EVALUATION FOR QUESTION 2 .................................... 1-11.1.1 Components Located Beyond the Outer Radius of the Reactor Core 1-21.1.2 Components Located Above the Reactor Core ................................... 1-21.1.3 Components Located Below the Reactor Core ................................... 1-32 R E FE R E N C E S .............................................................................................................. 2-1PWROG-1 5023-NP May 2015PVVROG-15023-NPMay 2015Revision 1 WESTINGHOUSE NON-PROPRIETARY CLASS 31-1MRP 2013-025 Guidance Text Demonstrating MRP-227-AApplicability for Seabrook Unit I Reactor Internals AgingManagement Fuel Design / Fuel Management AssessmentsIn Request for Additional Information (RAI) LRA Appendix B-1 [1], the U.S. NuclearRegulatory Commission (NRC) advised NextEra Energy Seabrook, LLC that theApplicant/Licensee Action Items (A/LAIs) for MRP-227-A would need to be resolved aspart of the staff's review of the Aging Management Program (AMP) for the ReactorVessel Internals (RVI) as part of the License Renewal Application (LRA) for SeabrookStation Unit 1.RAI LRA Appendix B-I -Aging Management of Reactor VesselInternals:The staff requests that the applicant provide either an LRA amendment or anupdate that includes updated AMP and AMR items for the PWR RVIcomponents at the Seabrook Station that are based on the guidance in LR-ISG-2011-04, including responses to applicable Applicant/License ActionsItems identified in the staffs SE for MRP-227 dated December 16, 2011.The NRC staff indicated [2] that information provided by the industry to the NRCstaff demonstrated that the MRP-227-A Inspection and Evaluation (I&E) Guidelinesare applicable for the range of conditions expected at the currently operatingWestinghouse and Combustion Engineering-deigned plants in the United States. Asa result of technical discussions with the NRC staff, the basis for a plant to respondto the NRC's RAI to demonstrate compliance with MRP-227-A for originally licensedand uprated conditions was determined to be satisfied with plant-specific responsesto the following two questions [2 and 3]:1. Does the plant have non-weld or bolting austenitic stainless steel (SS)components with 20 percent cold work or greater, and, if so, do the affectedcomponents have operating stresses greater than 30 ksi? (If both conditions aretrue, additional components may need to be screened in for stress corrosioncracking, SCC).2. Does the plant have atypical fuel deign or fuel management that could render theassumptions of MRP-227-A, regarding core loading/core design, non-representative for that plant?1.1 Seabrook Unit I Evaluation for Question 2Westinghouse has evaluated the Seabrook Station Unit 1 (NAH) reactor internalscomponents with regard to fuel designs and fuel management according to industryguideline MRP 2013-025 [4].PWROG-1 5023-NP May 2015Revision 1 WESTINGHOUSE NON-PROPRIETARY CLASS 31-2Seabrook Unit 1 has not utilized atypical fuel design or fuel management that could"make the assumptions of MRP-227-A regarding core loading/core design non-representative for that unit, including power changes/uprates that have occurred over theoperating lifetime of the unit. This conclusion is based on comparisons of the SeabrookUnit 1 core geometry and operating characteristics with the MRP-227-A applicabilityguidelines for Westinghouse-designed reactors specified in MRP 2013-025 [4].Specifically, the following comparisons with the MRP-227-A applicability guidelines inMRP 2013-025 [4] were established for the key reactor internals components atSeabrook Unit 1.1.1.1 Components Located Beyond the Outer Radius of the Reactor CoreGuideline 1 -The reactor has been operated with out-in fuel management for thirtyeffective full-power years or less and all future operation will use lowleakage fuel management.Comparison -Seabrook Unit 1 initiated low leakage fuel management strategy in thefourth fuel cycle following 2.99 effective full-power years (EFPY) ofoperation and has been implementing low leakage core designs sincethat time. There are no current plans to return to out-in fuelmanagement.Guideline 2 -For operation going forward the average power density of the reactorcore (as defined in MRP 2013-025 [4]) shall remain less than 124W/cm3.Comparison -For the last six operating fuel cycles (Cycles 12 through 17), SeabrookUnit I has been operating at a rated power level of 3648 MWt. For the193 fuel assembly Seabrook Unit 1 core geometry, the 3648 MWtpower level corresponds to a core power density of 111.8 W/cm3.Thislevel of power generation is also representative of anticipated futureoperation.Guideline 3 -For operation going forward, the nuclear heat generation rate figure ofmerit (HGR-FOM) (as defined in MRP 2013-025 [4]) shall not exceed68 W/cm3.Comparison -For the last six operating fuel cycles at Seabrook Unit 1, the HGR-FOM atkey baffle locations has ranged between [ a,c.This range of HGR-FOM is representative of anticipated future operation.1.1.2 Components Located Above the Reactor CoreGuideline 1 -Considering the entire operating lifetime of the reactor, the averagepower density of the core (as defined in MRP 2013-025 [4]) shallremain less than 124 W/cm3 for a period of more than two effective full-power years.PWROG-15023-NP May 2015Revision 1 WESTINGHOUSE NON-PROPRIETARY CLASS 31-3Comparison -Over the operating lifetime of the Seabrook Unit 1 reactor, the ratedcore power level, including power uprates, has varied between 3411MWI and 3648 MWt. This variation of rated power level correspondsto a power density range of 104.5 W/cm3to 111.8 W/cm3.Guideline 2 -Considering the entire operating lifetime of the reactor, the distancebetween the top of the active fuel stack and the bottom of the uppercore plate (UCP) shall not be less than 12.2 inches for a period ofmore than two effective full-power years.Comparison -For the Seabrook Unit 1 reactor internals and fuel assembly geometry,the nominal distance between the top of the active fuel stack and thebottom of the upper core plate (UCP) averaged over the first 17 fuelcycles of operation was [ Ia,c. During that period of timethe nominal distance between the UCP and the top of the active fuelwas not less than 12.2 inches for an operating period of more than twoeffective full-power years.1.1.3 Components Located Below the Reactor CoreBased on the discussion provided in MRP 2013-025 [4], plant-specific applicability ofMRP-227-A for components located below the reactor core with no further evaluationrequired is demonstrated by meeting the MRP-227-A, Section 2.4 criteria.PWROG-15023-NPMay 2015Revision 1 WESTINGHOUSE NON-PROPRIETARY CLASS 32-12 References1. U.S. NRC Letter, "Request for Additional Information Related to the Review of theSeabrook Station License Renewal Application -Set 21 (TAC NO. ME4028)," April 25,2014 (NRC ADAMS Accession No. ML14101A324)2. U.S. NRC Presentation, "Status of MRP-227-AAction Items 1 and 7," June 5, 2013.(NRC ADAMS Accession No. ML13154A1 52)3. U.S. NRC Letter, "Summary of February 25, 2013 Telecom with the Electric PowerResearch Institute and Westinghouse Electric Company," March 15, 2013. (NRCADAMS Accession No. ML1 3067A262)4. EPRI Letter, MRP 2013-025, "MRP-227-A Applicability Template Guideline," October 14,2013.PWROG-1 5023-NPMay 2015Revision 1}} | | .Rý.R :E1 SS- U R I Z E DPWROG'WAT E R R EýACjTO R R S G R.O U PPWROG.1I5023-NP IA Revi sionI" '... ... ...: : : ---. ............ .....-... ." : .: ., ' : ; ..--..: ..v ! : .WESTINGHOUSE NON-PROPRIETARY CLASS 3Seabrook Station Unit 1 SummaryReport for the Fuel Design / FuelManagement Assessments toDemonstrate MRP-227-A Applicability Materials Committee PA-MSC-0983, Revision. |
| | 1,Task 7May 2015Westinghouse WESTINGHOUSE NON-PROPRIETARY CLASS 3PWROG-15023-NP Revision 1Seabrook Station Unit I SummaryReport for the Fuel Design I FuelManagement Assessments toDemonstrate MRP-227-A Applicability PA-MSC-0983, Revision 1, Task 70983, Revision 1,Task 7Justin T. Figley*Safety Analysis and Licensing |
| | / LOCA Integrated Services IIMay 2015Reviewer: |
| | Jianwei Chen*Radiation Engineering and AnalysisApproved: |
| | Laurent P. Houssay*, |
| | ManagerRadiation Engineering and AnalysisApproved: |
| | James P. Molkenthin*, |
| | Program DirectorPWR Owners Group PMO*Electronically approved records are authenticated in the electronic document management system.Westinghouse Electric Company LLC1000 Westinghouse DriveCranberry |
| | : Township, PA 16066, USA© 2015 Westinghouse Electric Company LLCAll Rights Reserved WESTINGHOUSE NON-PROPRIETARY CLASS 3iiiACKNOWLEDGEMENTS This report was developed and funded by the Pressurized Water Reactor Owners Group underthe leadership of the participating utility representatives of the Materials Committee. |
| | PWROG-15023-NP May 2015Revision 1 |
| | WESTINGHOUSE NON-PROPRIETARY CLASS 3ivLEGAL NOTICEThis report was prepared as an account of work performed by Westinghouse ElectricCompany LLC. Neither Westinghouse Electric Company LLC, nor any person acting on itsbehalf:1. Makes any warranty or representation, express or implied including the warranties offitness for a particular purpose or merchantability, with respect to the accuracy, completeness, or usefulness of the information contained in this report, or that the use ofany information, apparatus, method, or process disclosed in this report may not infringeprivately owned rights; or2. Assumes any liabilities with respect to the use of, or for damages resulting from the useof, any information, apparatus, method, or process disclosed in this report.COPYRIGHT NOTICEThis report has been prepared by Westinghouse Electric Company LLC and bears aWestinghouse Electric Company copyright notice. As a member of the PWR Owners Group, youare permitted to copy and redistribute all or portions of the report within your organization; however all copies made by you must include the copyright notice in all instances. |
| | DISTRIBUTION NOTICEThis report was prepared for the PWR Owners Group. This Distribution Notice is intended toestablish guidance for access to this information. |
| | This report (including proprietary andnon-proprietary versions) is not to be provided to any individual or organization outside of thePWR Owners Group program participants without prior written approval of the PWR OwnersGroup Program Management Office. However, prior written approval is not required for programparticipants to provide copies of Class 3 Non-Proprietary reports to third parties that aresupporting implementation at their plant, and for submittals to the NRC.PWROG-1 5023-NP May 2015PWROG-1 5023-NPMay 2015Revision 1 |
| | WESTINGHOUSE NON-PROPRIETARY CLASS 3VTABLE OF CONTENTSMRP 2013-025 GUIDANCE TEXT DEMONSTRATING MRP-227-A APPLICABILITY FOR SEABROOK UNIT 1 REACTOR INTERNALS AGING MANAGEMENT FUELDESIGN / FUEL MANAGEMENT ASSESSMENTS |
| | ...................................................... |
| | 1-11.1 SEABROOK UNIT 1 EVALUATION FOR QUESTION 2 .................................... |
| | 1-11.1.1 Components Located Beyond the Outer Radius of the Reactor Core 1-21.1.2 Components Located Above the Reactor Core ................................... |
| | 1-21.1.3 Components Located Below the Reactor Core ................................... |
| | 1-32 R E FE R E N C E S .............................................................................................................. |
| | 2-1PWROG-1 5023-NP May 2015PVVROG-15023-NP May 2015Revision 1 |
| | WESTINGHOUSE NON-PROPRIETARY CLASS 31-1MRP 2013-025 Guidance Text Demonstrating MRP-227-A Applicability for Seabrook Unit I Reactor Internals AgingManagement Fuel Design / Fuel Management Assessments In Request for Additional Information (RAI) LRA Appendix B-1 [1], the U.S. NuclearRegulatory Commission (NRC) advised NextEra Energy Seabrook, LLC that theApplicant/Licensee Action Items (A/LAIs) for MRP-227-A would need to be resolved aspart of the staff's review of the Aging Management Program (AMP) for the ReactorVessel Internals (RVI) as part of the License Renewal Application (LRA) for SeabrookStation Unit 1.RAI LRA Appendix B-I -Aging Management of Reactor VesselInternals: |
| | The staff requests that the applicant provide either an LRA amendment or anupdate that includes updated AMP and AMR items for the PWR RVIcomponents at the Seabrook Station that are based on the guidance in LR-ISG-2011-04, including responses to applicable Applicant/License ActionsItems identified in the staffs SE for MRP-227 dated December 16, 2011.The NRC staff indicated |
| | [2] that information provided by the industry to the NRCstaff demonstrated that the MRP-227-A Inspection and Evaluation (I&E) Guidelines are applicable for the range of conditions expected at the currently operating Westinghouse and Combustion Engineering-deigned plants in the United States. Asa result of technical discussions with the NRC staff, the basis for a plant to respondto the NRC's RAI to demonstrate compliance with MRP-227-A for originally licensedand uprated conditions was determined to be satisfied with plant-specific responses to the following two questions |
| | [2 and 3]:1. Does the plant have non-weld or bolting austenitic stainless steel (SS)components with 20 percent cold work or greater, and, if so, do the affectedcomponents have operating stresses greater than 30 ksi? (If both conditions aretrue, additional components may need to be screened in for stress corrosion |
| | : cracking, SCC).2. Does the plant have atypical fuel deign or fuel management that could render theassumptions of MRP-227-A, regarding core loading/core design, non-representative for that plant?1.1 Seabrook Unit I Evaluation for Question 2Westinghouse has evaluated the Seabrook Station Unit 1 (NAH) reactor internals components with regard to fuel designs and fuel management according to industryguideline MRP 2013-025 |
| | [4].PWROG-1 5023-NP May 2015Revision 1 |
| | WESTINGHOUSE NON-PROPRIETARY CLASS 31-2Seabrook Unit 1 has not utilized atypical fuel design or fuel management that could"make the assumptions of MRP-227-A regarding core loading/core design non-representative for that unit, including power changes/uprates that have occurred over theoperating lifetime of the unit. This conclusion is based on comparisons of the SeabrookUnit 1 core geometry and operating characteristics with the MRP-227-A applicability guidelines for Westinghouse-designed reactors specified in MRP 2013-025 |
| | [4].Specifically, the following comparisons with the MRP-227-A applicability guidelines inMRP 2013-025 |
| | [4] were established for the key reactor internals components atSeabrook Unit 1.1.1.1 Components Located Beyond the Outer Radius of the Reactor CoreGuideline 1 -The reactor has been operated with out-in fuel management for thirtyeffective full-power years or less and all future operation will use lowleakage fuel management. |
| | Comparison |
| | -Seabrook Unit 1 initiated low leakage fuel management strategy in thefourth fuel cycle following 2.99 effective full-power years (EFPY) ofoperation and has been implementing low leakage core designs sincethat time. There are no current plans to return to out-in fuelmanagement. |
| | Guideline 2 -For operation going forward the average power density of the reactorcore (as defined in MRP 2013-025 |
| | [4]) shall remain less than 124W/cm3.Comparison |
| | -For the last six operating fuel cycles (Cycles 12 through 17), SeabrookUnit I has been operating at a rated power level of 3648 MWt. For the193 fuel assembly Seabrook Unit 1 core geometry, the 3648 MWtpower level corresponds to a core power density of 111.8 W/cm3.Thislevel of power generation is also representative of anticipated futureoperation. |
| | Guideline 3 -For operation going forward, the nuclear heat generation rate figure ofmerit (HGR-FOM) |
| | (as defined in MRP 2013-025 |
| | [4]) shall not exceed68 W/cm3.Comparison |
| | -For the last six operating fuel cycles at Seabrook Unit 1, the HGR-FOM atkey baffle locations has ranged between [ a,c.This range of HGR-FOM is representative of anticipated future operation. |
| | 1.1.2 Components Located Above the Reactor CoreGuideline 1 -Considering the entire operating lifetime of the reactor, the averagepower density of the core (as defined in MRP 2013-025 |
| | [4]) shallremain less than 124 W/cm3 for a period of more than two effective full-power years.PWROG-15023-NP May 2015Revision 1 |
| | WESTINGHOUSE NON-PROPRIETARY CLASS 31-3Comparison |
| | -Over the operating lifetime of the Seabrook Unit 1 reactor, the ratedcore power level, including power uprates, has varied between 3411MWI and 3648 MWt. This variation of rated power level corresponds to a power density range of 104.5 W/cm3to 111.8 W/cm3.Guideline 2 -Considering the entire operating lifetime of the reactor, the distancebetween the top of the active fuel stack and the bottom of the uppercore plate (UCP) shall not be less than 12.2 inches for a period ofmore than two effective full-power years.Comparison |
| | -For the Seabrook Unit 1 reactor internals and fuel assembly |
| | : geometry, the nominal distance between the top of the active fuel stack and thebottom of the upper core plate (UCP) averaged over the first 17 fuelcycles of operation was [ Ia,c. During that period of timethe nominal distance between the UCP and the top of the active fuelwas not less than 12.2 inches for an operating period of more than twoeffective full-power years.1.1.3 Components Located Below the Reactor CoreBased on the discussion provided in MRP 2013-025 |
| | [4], plant-specific applicability ofMRP-227-A for components located below the reactor core with no further evaluation required is demonstrated by meeting the MRP-227-A, Section 2.4 criteria. |
| | PWROG-15023-NP May 2015Revision 1 |
| | WESTINGHOUSE NON-PROPRIETARY CLASS 32-12 References |
| | : 1. U.S. NRC Letter, "Request for Additional Information Related to the Review of theSeabrook Station License Renewal Application |
| | -Set 21 (TAC NO. ME4028)," |
| | April 25,2014 (NRC ADAMS Accession No. ML14101A324) |
| | : 2. U.S. NRC Presentation, "Status of MRP-227-AAction Items 1 and 7," June 5, 2013.(NRC ADAMS Accession No. ML13154A1 52)3. U.S. NRC Letter, "Summary of February 25, 2013 Telecom with the Electric PowerResearch Institute and Westinghouse Electric Company," |
| | March 15, 2013. (NRCADAMS Accession No. ML1 3067A262) |
| | : 4. EPRI Letter, MRP 2013-025, "MRP-227-A Applicability Template Guideline," |
| | October 14,2013.PWROG-1 5023-NPMay 2015Revision 1}} |
Letter Sequence Other |
---|
TAC:ME4028, Steam Generator Tube Integrity (Approved, Closed) |
Results
Other: ML103620318, ML110270026, ML110280424, ML110970260, ML11280A045, ML11304A002, ML11304A109, ML12009A007, ML12164A756, ML12164A759, ML12214A607, ML12242A198, ML12264A648, ML13261A145, ML15149A280, ML15149A282, ML15183A020, ML15287A017, ML15307A022, ML15310A102, ML15337A047, ML15343A186, ML15349A918, ML19205A362, ML19205A365, ML19205A389, SBK-L-15073, Responses to Applicant/Licensee Action Items for the Inspection and Evaluation Guidelines for Pressurized Water Reactor Vessel Internals (MRP-227-A)
|
MONTHYEARML1036203182010-01-21021 January 2010 Attachment 2, Document SEA-FLU-001-R-004, Rev 0, Non-Proprietary Version of Seabrook Station Reactor Pressure Vessel Fluence Evaluation at 55 EFPY Project stage: Other ML1022205712010-08-10010 August 2010 License Renewal Process Overview and Scoping Public Meeting Slides Project stage: Meeting ML1025202222010-09-20020 September 2010 Summary of Public License Renewal Overview and Environmental Scoping Meeting Related to the Review of the Seabrook Station License Renewal Application (TAC No. ME3959 and ME4028) Project stage: Meeting ML11307A1392010-10-28028 October 2010 2010/10/28 Seabrook Lr - FW: Seabrook Station, Unit No. 1 - Fire Protection Request for Additional Information Regarding License Renewal Application Project stage: RAI SBK-L-10192, Supplement 2 to License Renewal Application2010-11-15015 November 2010 Supplement 2 to License Renewal Application Project stage: Supplement ML1030905582010-11-18018 November 2010 Request for Additional Information Related to the Review of the Seabrook Station, License Renewal Application - Aging Management Programs Project stage: RAI ML1030903082010-11-18018 November 2010 Request for Additional Information Related to the Review of the Seabrook Station, License Renewal Application Project stage: RAI ML1031301592010-11-18018 November 2010 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI ML1032605542010-12-14014 December 2010 Request for Additional Information Related to the Review of the Seabrook Station, License Renewal Application (TAC No. ME4028) Aging-Management Programs Project stage: RAI ML1034202732010-12-14014 December 2010 Request for Additional Information Related to the Review of the Seabrook Station, License Renewal Application (TAC No. ME4028) - Aging Management Programs Project stage: RAI SBK-L-10204, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs2010-12-17017 December 2010 Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs Project stage: Response to RAI SBK-L-10203, Response to Request for Additional Information Set 2 Related to the Review of the License Renewal Application2010-12-22022 December 2010 Response to Request for Additional Information Set 2 Related to the Review of the License Renewal Application Project stage: Response to RAI ML1034205872011-01-0505 January 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI ML1034205852011-01-0505 January 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI ML1034205832011-01-0505 January 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI SBK-L-11003, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs - Set 52011-01-13013 January 2011 Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs - Set 5 Project stage: Response to RAI SBK-L-11002, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs - Set 42011-01-13013 January 2011 Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Aging Management Programs - Set 4 Project stage: Response to RAI ML1100701282011-01-21021 January 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI SBK-L-11015, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Sets 6, 7 and 82011-02-0303 February 2011 Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Sets 6, 7 and 8 Project stage: Response to RAI ML1102700262011-02-0404 February 2011 Scoping and Screening Audit Summary Regarding the Seabrook Station License Renewal Application (TAC Number ME4028) Project stage: Other SBK-L-11027, Response to Request for Additional Information, License Renewal Application, Request for Additional Information - Set 92011-02-18018 February 2011 Response to Request for Additional Information, License Renewal Application, Request for Additional Information - Set 9 Project stage: Response to RAI ML1102602662011-02-24024 February 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI ML1105509202011-03-0707 March 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI ML1103506302011-03-17017 March 2011 Letter Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI ML1102804242011-03-21021 March 2011 Audit Report Regarding the Seabrook Station License Renewal Application Project stage: Other ML1109702602011-03-28028 March 2011 Nwt 817, Chemistry Control in the Seabrook Thermal Barrier Loop, Final Project stage: Other ML1107000182011-03-30030 March 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI SBK-L-11062, Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Request for Additional Information - Set 112011-04-0505 April 2011 Response to Request for Additional Information NextEra Energy Seabrook License Renewal Application Request for Additional Information - Set 11 Project stage: Response to RAI SBK-L-11069, Response to Request for Additional Information - Set 12 and Associated License Renewal Application Changes2011-04-22022 April 2011 Response to Request for Additional Information - Set 12 and Associated License Renewal Application Changes Project stage: Response to RAI ML11132A0072011-05-23023 May 2011 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application Project stage: RAI SBK-L-11123, Response to Request for Additional Information, NextEra Energy Seabrook License Renewal Application, Request for Additional Information - Set 142011-06-0202 June 2011 Response to Request for Additional Information, NextEra Energy Seabrook License Renewal Application, Request for Additional Information - Set 14 Project stage: Response to RAI ML11139A1462011-06-0909 June 2011 Summary of Telephone Conference Call Held Between the NRC and Nextera Energy Seabrook, LLC, to Clarify Responses to RAI and Draft Requests for Additional Information Pertaining to the Seabrook Station LRA Project stage: Draft RAI ML11143A1652011-06-15015 June 2011 5/18/11, Summary of Telephone Conference Call Held Between NRC and Nextera Energy Seabrook, LLC, Concerning the D-RAI Pertaining to the Seabrook Station License Renewal Application Project stage: RAI SBK-L-11133, Response to Request for Additional Information - Set 14 RAI B.1.4-12011-06-24024 June 2011 Response to Request for Additional Information - Set 14 RAI B.1.4-1 Project stage: Response to RAI ML11178A3652011-07-12012 July 2011 Schedule Revision for the Safety Review of the Seabrook Station License Renewal Application Project stage: Approval ML11284A0202011-10-14014 October 2011 Summary of Telephone Conf Call Held on August 4, 2011 Between the USNRC and Nextera Energy Seabrook, Llc., Concerning Clarification of Information Pertaining to the Seabrook Station Request for Additional Information Response Project stage: RAI ML11280A0452011-10-17017 October 2011 Summary of Telephone Conference Call Held on May 5, 2011, Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook, LLC, Concerning Clarification of Information Pertaining to the Seabrook Station LRA Project stage: Other ML11304A0022011-11-0404 November 2011 Summary of Tele Conf Call Held on 3/18/11, Between the USNRC and NextEra Energy Seabrook, Llc., Concerning Clarification of Information Pertaining to the Seabrook Station License Renewal Application Project stage: Other ML11304A1092011-11-0404 November 2011 Summary of Tele Conf Call Held on 5/31/11, Between the USNRC and Nextera Energy Seabrook, Llc., Concerning Clarification of Information Pertaining to the Seabrook LRA Project stage: Other ML11304A1512011-11-0404 November 2011 Summary of Tele Conf Call Held on 4/8/11 Between USNRC and NextEra Energy Seabrook, Llc. Concerning Clarification of Information Pertaining to the Seabrook Station Request for Additional Information Responses Project stage: RAI ML11304A1662011-11-0404 November 2011 Summary of Tele Conf Call Held on 3/3/11, Between the USNRC and NextEra Energy Seabrook, Llc. Concerning Clarification of Information Pertaining to the Seabrook Station Request for Additional Information Responses Project stage: RAI ML12009A0072012-01-25025 January 2012 Project Manager Change for the License Renewal of Seabrook Station Project stage: Other ML12054A7662012-03-26026 March 2012 022312, Telecon Summary Between NRC and NextEra Seabrook, Discussing RAIs Response Project stage: RAI ML12160A3742012-06-0808 June 2012 Safety Evaluation Report with Open Items Related to the License Renewal of Seabrook Station Project stage: Approval ML12053A1922012-06-0808 June 2012 Safety Evaluation Report with Open Items Related to the License Renewal of Seabrook Station (TAC No. ME4028). Seabrook SER with Open Items Transmittal Letter Project stage: Approval ML12165A7422012-06-21021 June 2012 Summary of Telephone Conference Call Held on April 10, 2012, Between NRC and Energy Seabrook, LLC, Concerning the Response to Request for Additional Information Pertaining to the Seabrook Station LRA Project stage: RAI ML12165A5952012-06-22022 June 2012 Summary of Telephone Conference Call Held on May 16, 2012, Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook, LLC, Concerning the Response to Request for Additional Information Pertaining to the Seabrook Station LRA Project stage: RAI ML12164A9012012-06-22022 June 2012 Summary of Telephone Conference Call Held on 5/24/12, Between the NRC and NextEra Energy Seabrook, LLC Concerning the Drai Pertaining to the Seabrook Station LRA Project stage: RAI ML12164A7562012-06-22022 June 2012 Summary of Telephone Conference Call Between NRC and NextEra Seabrook Project stage: Other ML12164A7592012-07-0303 July 2012 041912, Telecon Summary Between NRC and NextEra Seabrook Project stage: Other 2011-02-04
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PWROG-15023-NP, Revision 1, Seabrook Station, Unit 1, Summary Report for the Fuel Design / Fuel Management Assessments to Demonstrate MRP-227-A Applicability.ML15149A282 |
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Seabrook ![NextEra Energy icon.png](/w/images/9/9b/NextEra_Energy_icon.png) |
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05/31/2015 |
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From: |
Chen J, Figley J T, Houssay L P, Molkenthin J P PWR Owners Group, Westinghouse |
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Document Control Desk, Office of Nuclear Reactor Regulation |
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ML15149A278 |
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MRP-227-A, SBK-L-15073, TAC ME4028 PWROG-15023-NP, Rev. 1 |
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Category:Topical Report
MONTHYEARL-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2022-082, NextEra Energy Seabrook, LLC, and NextEra Energy Point Beach, LLC, Quality Assurance Topical Report FPL-1, Revision 282022-05-23023 May 2022 NextEra Energy Seabrook, LLC, and NextEra Energy Point Beach, LLC, Quality Assurance Topical Report FPL-1, Revision 28 L-2021-234, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 27 Update2021-12-15015 December 2021 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 27 Update L-2021-115, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 26 Annual Submittal and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 102021-05-24024 May 2021 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 26 Annual Submittal and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 10 L-2016-129, NextEra Energy Quality Assurance Topical Report (QATR FPL-1) Revision 19 Annual Submittal2016-06-22022 June 2016 NextEra Energy Quality Assurance Topical Report (QATR FPL-1) Revision 19 Annual Submittal ML15149A2822015-05-31031 May 2015 PWROG-15023-NP, Revision 1, Seabrook Station, Unit 1, Summary Report for the Fuel Design / Fuel Management Assessments to Demonstrate MRP-227-A Applicability. ML15149A2802015-05-31031 May 2015 PWROG-14083-NP, Revision 1, NextEra Energy, Seabrook Unit 1, Summary Report for Applicant/Licensee Action Items 1, 2, and 7. ML15149A2832015-05-26026 May 2015 PWROG-15042-P, Revision 0, Appendix a, NextEra Energy, Seabrook, Unit 1, Summary Report for the Cold Work Assessment (Non-Proprietary). Application for Withholding Proprietary Information from Disclosure and Affidavit L-2013-208, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 132013-07-0101 July 2013 Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 13 SBK-L-12256, WCAP-17441-NP, Rev 0, Seabrook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation2011-10-31031 October 2011 WCAP-17441-NP, Rev 0, Seabrook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation L-2010-138, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 72010-06-28028 June 2010 Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 7 L-2009-134, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 42009-06-29029 June 2009 Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 4 ML0913404382009-04-30030 April 2009 Westinghouse Electric Co., WCAP-17071-NP, Revision 0, H: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F) L-2008-150, Duane Arnold, and Point, Beach, Units 1 and 2, Quality Assurance Topical Report (QATR-FPL-1) Revisions 1 & 22008-06-27027 June 2008 Duane Arnold, and Point, Beach, Units 1 and 2, Quality Assurance Topical Report (QATR-FPL-1) Revisions 1 & 2 L-2006-246, Response to RAI Follow-Up Questions Regarding Fpl'S Common Quality Assurance Topical Report Request2006-11-15015 November 2006 Response to RAI Follow-Up Questions Regarding Fpl'S Common Quality Assurance Topical Report Request ML0615203362006-04-30030 April 2006 WCAP-16550-NP, Rev. 0, Stuctural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Opearation: Seabrook Station. L-2006-067, Request for Approval of FPL Quality Assurance Topical Report2006-03-31031 March 2006 Request for Approval of FPL Quality Assurance Topical Report ML0610300882006-03-31031 March 2006 WCAP-16526-NP, Rev. 0, Analysis of Capsule V from FPL Energy - Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program. ML0332302252003-11-12012 November 2003 Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application. 2024-07-10
[Table view] |
Text
Enclosure 7 to SBK-L-15073 Non-Proprietary Class 3 Westinghouse Report (PWROG-15023-NP, Revision 1)Seabrook Station Unit 1 Summary ReportFor the Fuel Design/Fuel Management Assessments toDemonstrate MRP-227-A Applicability (Non-Proprietary)
.Rý.R :E1 SS- U R I Z E DPWROG'WAT E R R EýACjTO R R S G R.O U PPWROG.1I5023-NP IA Revi sionI" '... ... ...: : : ---. ............ .....-... ." : .: ., ' : ; ..--..: ..v ! : .WESTINGHOUSE NON-PROPRIETARY CLASS 3Seabrook Station Unit 1 SummaryReport for the Fuel Design / FuelManagement Assessments toDemonstrate MRP-227-A Applicability Materials Committee PA-MSC-0983, Revision.
1,Task 7May 2015Westinghouse WESTINGHOUSE NON-PROPRIETARY CLASS 3PWROG-15023-NP Revision 1Seabrook Station Unit I SummaryReport for the Fuel Design I FuelManagement Assessments toDemonstrate MRP-227-A Applicability PA-MSC-0983, Revision 1, Task 70983, Revision 1,Task 7Justin T. Figley*Safety Analysis and Licensing
/ LOCA Integrated Services IIMay 2015Reviewer:
Jianwei Chen*Radiation Engineering and AnalysisApproved:
Laurent P. Houssay*,
ManagerRadiation Engineering and AnalysisApproved:
James P. Molkenthin*,
Program DirectorPWR Owners Group PMO*Electronically approved records are authenticated in the electronic document management system.Westinghouse Electric Company LLC1000 Westinghouse DriveCranberry
- Township, PA 16066, USA© 2015 Westinghouse Electric Company LLCAll Rights Reserved WESTINGHOUSE NON-PROPRIETARY CLASS 3iiiACKNOWLEDGEMENTS This report was developed and funded by the Pressurized Water Reactor Owners Group underthe leadership of the participating utility representatives of the Materials Committee.
PWROG-15023-NP May 2015Revision 1
WESTINGHOUSE NON-PROPRIETARY CLASS 3ivLEGAL NOTICEThis report was prepared as an account of work performed by Westinghouse ElectricCompany LLC. Neither Westinghouse Electric Company LLC, nor any person acting on itsbehalf:1. Makes any warranty or representation, express or implied including the warranties offitness for a particular purpose or merchantability, with respect to the accuracy, completeness, or usefulness of the information contained in this report, or that the use ofany information, apparatus, method, or process disclosed in this report may not infringeprivately owned rights; or2. Assumes any liabilities with respect to the use of, or for damages resulting from the useof, any information, apparatus, method, or process disclosed in this report.COPYRIGHT NOTICEThis report has been prepared by Westinghouse Electric Company LLC and bears aWestinghouse Electric Company copyright notice. As a member of the PWR Owners Group, youare permitted to copy and redistribute all or portions of the report within your organization; however all copies made by you must include the copyright notice in all instances.
DISTRIBUTION NOTICEThis report was prepared for the PWR Owners Group. This Distribution Notice is intended toestablish guidance for access to this information.
This report (including proprietary andnon-proprietary versions) is not to be provided to any individual or organization outside of thePWR Owners Group program participants without prior written approval of the PWR OwnersGroup Program Management Office. However, prior written approval is not required for programparticipants to provide copies of Class 3 Non-Proprietary reports to third parties that aresupporting implementation at their plant, and for submittals to the NRC.PWROG-1 5023-NP May 2015PWROG-1 5023-NPMay 2015Revision 1
WESTINGHOUSE NON-PROPRIETARY CLASS 3VTABLE OF CONTENTSMRP 2013-025 GUIDANCE TEXT DEMONSTRATING MRP-227-A APPLICABILITY FOR SEABROOK UNIT 1 REACTOR INTERNALS AGING MANAGEMENT FUELDESIGN / FUEL MANAGEMENT ASSESSMENTS
......................................................
1-11.1 SEABROOK UNIT 1 EVALUATION FOR QUESTION 2 ....................................
1-11.1.1 Components Located Beyond the Outer Radius of the Reactor Core 1-21.1.2 Components Located Above the Reactor Core ...................................
1-21.1.3 Components Located Below the Reactor Core ...................................
1-32 R E FE R E N C E S ..............................................................................................................
2-1PWROG-1 5023-NP May 2015PVVROG-15023-NP May 2015Revision 1
WESTINGHOUSE NON-PROPRIETARY CLASS 31-1MRP 2013-025 Guidance Text Demonstrating MRP-227-A Applicability for Seabrook Unit I Reactor Internals AgingManagement Fuel Design / Fuel Management Assessments In Request for Additional Information (RAI) LRA Appendix B-1 [1], the U.S. NuclearRegulatory Commission (NRC) advised NextEra Energy Seabrook, LLC that theApplicant/Licensee Action Items (A/LAIs) for MRP-227-A would need to be resolved aspart of the staff's review of the Aging Management Program (AMP) for the ReactorVessel Internals (RVI) as part of the License Renewal Application (LRA) for SeabrookStation Unit 1.RAI LRA Appendix B-I -Aging Management of Reactor VesselInternals:
The staff requests that the applicant provide either an LRA amendment or anupdate that includes updated AMP and AMR items for the PWR RVIcomponents at the Seabrook Station that are based on the guidance in LR-ISG-2011-04, including responses to applicable Applicant/License ActionsItems identified in the staffs SE for MRP-227 dated December 16, 2011.The NRC staff indicated
[2] that information provided by the industry to the NRCstaff demonstrated that the MRP-227-A Inspection and Evaluation (I&E) Guidelines are applicable for the range of conditions expected at the currently operating Westinghouse and Combustion Engineering-deigned plants in the United States. Asa result of technical discussions with the NRC staff, the basis for a plant to respondto the NRC's RAI to demonstrate compliance with MRP-227-A for originally licensedand uprated conditions was determined to be satisfied with plant-specific responses to the following two questions
[2 and 3]:1. Does the plant have non-weld or bolting austenitic stainless steel (SS)components with 20 percent cold work or greater, and, if so, do the affectedcomponents have operating stresses greater than 30 ksi? (If both conditions aretrue, additional components may need to be screened in for stress corrosion
- cracking, SCC).2. Does the plant have atypical fuel deign or fuel management that could render theassumptions of MRP-227-A, regarding core loading/core design, non-representative for that plant?1.1 Seabrook Unit I Evaluation for Question 2Westinghouse has evaluated the Seabrook Station Unit 1 (NAH) reactor internals components with regard to fuel designs and fuel management according to industryguideline MRP 2013-025
[4].PWROG-1 5023-NP May 2015Revision 1
WESTINGHOUSE NON-PROPRIETARY CLASS 31-2Seabrook Unit 1 has not utilized atypical fuel design or fuel management that could"make the assumptions of MRP-227-A regarding core loading/core design non-representative for that unit, including power changes/uprates that have occurred over theoperating lifetime of the unit. This conclusion is based on comparisons of the SeabrookUnit 1 core geometry and operating characteristics with the MRP-227-A applicability guidelines for Westinghouse-designed reactors specified in MRP 2013-025
[4].Specifically, the following comparisons with the MRP-227-A applicability guidelines inMRP 2013-025
[4] were established for the key reactor internals components atSeabrook Unit 1.1.1.1 Components Located Beyond the Outer Radius of the Reactor CoreGuideline 1 -The reactor has been operated with out-in fuel management for thirtyeffective full-power years or less and all future operation will use lowleakage fuel management.
Comparison
-Seabrook Unit 1 initiated low leakage fuel management strategy in thefourth fuel cycle following 2.99 effective full-power years (EFPY) ofoperation and has been implementing low leakage core designs sincethat time. There are no current plans to return to out-in fuelmanagement.
Guideline 2 -For operation going forward the average power density of the reactorcore (as defined in MRP 2013-025
[4]) shall remain less than 124W/cm3.Comparison
-For the last six operating fuel cycles (Cycles 12 through 17), SeabrookUnit I has been operating at a rated power level of 3648 MWt. For the193 fuel assembly Seabrook Unit 1 core geometry, the 3648 MWtpower level corresponds to a core power density of 111.8 W/cm3.Thislevel of power generation is also representative of anticipated futureoperation.
Guideline 3 -For operation going forward, the nuclear heat generation rate figure ofmerit (HGR-FOM)
(as defined in MRP 2013-025
[4]) shall not exceed68 W/cm3.Comparison
-For the last six operating fuel cycles at Seabrook Unit 1, the HGR-FOM atkey baffle locations has ranged between [ a,c.This range of HGR-FOM is representative of anticipated future operation.
1.1.2 Components Located Above the Reactor CoreGuideline 1 -Considering the entire operating lifetime of the reactor, the averagepower density of the core (as defined in MRP 2013-025
[4]) shallremain less than 124 W/cm3 for a period of more than two effective full-power years.PWROG-15023-NP May 2015Revision 1
WESTINGHOUSE NON-PROPRIETARY CLASS 31-3Comparison
-Over the operating lifetime of the Seabrook Unit 1 reactor, the ratedcore power level, including power uprates, has varied between 3411MWI and 3648 MWt. This variation of rated power level corresponds to a power density range of 104.5 W/cm3to 111.8 W/cm3.Guideline 2 -Considering the entire operating lifetime of the reactor, the distancebetween the top of the active fuel stack and the bottom of the uppercore plate (UCP) shall not be less than 12.2 inches for a period ofmore than two effective full-power years.Comparison
-For the Seabrook Unit 1 reactor internals and fuel assembly
- geometry, the nominal distance between the top of the active fuel stack and thebottom of the upper core plate (UCP) averaged over the first 17 fuelcycles of operation was [ Ia,c. During that period of timethe nominal distance between the UCP and the top of the active fuelwas not less than 12.2 inches for an operating period of more than twoeffective full-power years.1.1.3 Components Located Below the Reactor CoreBased on the discussion provided in MRP 2013-025
[4], plant-specific applicability ofMRP-227-A for components located below the reactor core with no further evaluation required is demonstrated by meeting the MRP-227-A, Section 2.4 criteria.
PWROG-15023-NP May 2015Revision 1
WESTINGHOUSE NON-PROPRIETARY CLASS 32-12 References
- 1. U.S. NRC Letter, "Request for Additional Information Related to the Review of theSeabrook Station License Renewal Application
-Set 21 (TAC NO. ME4028),"
April 25,2014 (NRC ADAMS Accession No. ML14101A324)
- 2. U.S. NRC Presentation, "Status of MRP-227-AAction Items 1 and 7," June 5, 2013.(NRC ADAMS Accession No. ML13154A1 52)3. U.S. NRC Letter, "Summary of February 25, 2013 Telecom with the Electric PowerResearch Institute and Westinghouse Electric Company,"
March 15, 2013. (NRCADAMS Accession No. ML1 3067A262)
- 4. EPRI Letter, MRP 2013-025, "MRP-227-A Applicability Template Guideline,"
October 14,2013.PWROG-1 5023-NPMay 2015Revision 1